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Simulation of in-core dose rates for an offline CANDU reactor
(2016-04-01)
This thesis describes the development of a Monte Carlo simulation to predict the dose rates that will be encountered by a novel robotic inspection system for the pressure tubes of an offline CANDU reactor. Simulations were ...
Examination of secondary electrons generated by encapsulated gamma sources to improve contact dosimetry estimates
(2017-04-01)
Secondary electron generation on the surface of encapsulated gamma sources can play a large role in the dose measured near the surface of the encapsulation. The National Council on Radiation Protection and Measurements ...
Characterization of neutron fields around an intense neutron generator
(2016-12-01)
Neutron fields in the vicinity of the University of Ontario Institute of Technology neutron facility have been investigated in a series of simulations and experiments. The neutron fluence at several locations around the ...
Low energy photon mimic of the tritium beta decay energy spectrum
(2013-04-01)
Tritium is a radioactive hydrogen isotope that is typically produced via neutron interaction with heavy water (D2O), producing tritiated water (DTO). As a result of this, tritium accounts for roughly a third of all ...
Leakage-corrected discontinuity factors for a second-generation Th-Pu pressure-tube SCWR.
(2014-08-01)
The neutron flux throughout a reactor core should be calculated, ideally, by solving the neutron transport equation for a highly detailed geometric model of the core. Since this is computationally impractical, approximate ...
Investigation of sub-cell homogenization for PHWR lattice cells using superhomogenization factors
(2016-12-01)
To avoid the computational effort associated with full-core neutron transport calculations, full-core neutronics calculations for Pressurized Heavy-Water Reactors (PHWRs) are usually performed in diffusion theory using an ...
Study of fuzzy logic in safety and control systems in nuclear power plants
(2016-03-01)
Safety and control systems in Nuclear Power Plants are essentially run without intelligent systems. As nuclear industry starts to become more advanced and vendors are starting to manufacture more advance products, old ...
Specifics of forced-convection heat transfer to supercritical water flowing upward in annular and bundle flow geometries
(2016-08-01)
Since annulus- and bundle-flow geometries impede coolant flow, heat transfer to the coolant would occur differently than in bare tubes. The main objective of this work is to propose and verity a universal method to accurately ...
Development of a 37-element fuel bundle for the production of molybdenum-99 in CANDU power reactors.
(2014-08-01)
In this study, the potential use of CANDU power reactors for the production of Mo-99 is assessed. Five different modifications of a 37-element fuel bundle that could be used for the production of Mo-99 in existing CANDU ...
Assessment of FLUENT CFD code as an analysis tool for SCW applications
(2012-08-01)
Chosen as one of six Generation‒IV nuclear-reactor concepts, SuperCritical Water-cooled Reactors (SCWRs) are expected to have high thermal efficiencies within the range of 45 ‒ 50% owing to the reactor‟s high pressures and ...